Development and validation of a new multigroup Monte Carlo Criticality Calculations (MC3) code-Reference-Cited by-同舟云学术

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Development and validation of a new multigroup Monte Carlo Criticality Calculations (MC3) code

Published:2015-05 Issue: Volume:81 Page:53-59
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Zangian M.,Minuchehr A.,Zolfaghari A.

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference22 articles.

1. VIM Monte Carlo Neutron/Photon Transport Code, User's Guide Version 5.1;Blomquist,2009

2. High performance computing and Monte Carlo;Brown;Trans. Am. Nucl. Soc.,2004

3. Exploring Monte Carlo Methods;Dunn,2011

4. MORSE-CGA, a Monte Carlo Radiation Transport Code with Array Geometry Capability;Emmett,1985

5. Overview of Monte Carlo radiation transport codes;Kirk;Radiat. Meas.,2010

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1. Development of multi-group Monte-Carlo transport and depletion coupling calculation method and verification with metal-fueled fast reactor;Nuclear Science and Techniques;2023-11

2. A pure dynamic Monte Carlo code for the neutronic analysis of nuclear reactors;Annals of Nuclear Energy;2022-01

3. Implementation and comparison of different prompt and delayed α-static approaches;Progress in Nuclear Energy;2019-07

4. An improved convergence rate for the prompt α eigenvalue calculation in α-k iteration methods;Annals of Nuclear Energy;2018-08

5. ENTRANS: A platform for finite elements modeling of 3D neutron transport equation, Part II. Multidimensional implementation;Annals of Nuclear Energy;2017-03

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